Uncertainty and sensitivity analysis in the neutronic parameters generation for BWR and PWR coupled thermal-hydraulic-neutronic simulations

被引：8

作者：

Anchel, F. ^{[1
]}

Barrachina, T. ^{[1
]}

Miro, R. ^{[1
]}

Verdu, G. ^{[1
]}

Juanas, J. ^{[2
]}

Macian-Juan, R. ^{[2
]}

机构：

[1] Univ Politecn Valencia UPV, Inst Ind Radiophys & Environm Safety ISIRYM, Valencia 46021, Spain

[2] Tech Univ Munich, Lehrstuhl Nukl Tech, D-85747 Garching, Germany

来源：

NUCLEAR ENGINEERING AND DESIGN | 2012年 / 246卷

关键词：

D O I：

10.1016/j.nucengdes.2011.11.016

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

The Best Estimate analysis consists of a coupled thermal-hydraulic and neutronic description of the nuclear system's behavior; uncertainties from both aspects should be included and jointly propagated. This paper presents a study of the influence of the uncertainty in the macroscopic neutronic information that describes a three-dimensional core model on the most relevant results of the simulation of a Reactivity Induced Accident (RIA). The analyses of a BWR-RIA and a PWR-RIA have been carried out with a three-dimensional thermal-hydraulic and neutronic model for the coupled system TRACE-PARCS and RELAP-PARCS. The cross section information has been generated by the SIMTAB methodology based on the joint use of CASMO-SIMULATE. The statistically based methodology performs a Monte-Carlo kind of sampling of the uncertainty in the macroscopic cross sections. The size of the sampling is determined by the characteristics of the tolerance intervals by applying the Noether-Wilks formulas. A number of simulations equal to the sample size have been carried out in which the cross sections used by PARCS are directly modified with uncertainty, and non-parametric statistical methods are applied to the resulting sample of the values of the output variables to determine their intervals of tolerance. (C) 2011 Elsevier B.V. All rights reserved.

引用

页码：98 / 106

页数：9